ICONE29-91811 Investigation the Fuel Damage Fraction of IB-LOCA

ICONE29-91811 Investigation the Fuel Damage Fraction of IB-LOCA

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 7, A
1. Verfasser: Yue, Zhidong (VerfasserIn)
Weitere Verfasser: Wei, Ting (VerfasserIn), Cai, Wei (VerfasserIn), Ke, Xiao (VerfasserIn), Zhang, Ying (VerfasserIn)
Pages:2022 29
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2022
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
ICONE29-88830 Effect of the Virtual Mass Force Term on the Critical Flow 2022 Xu, Hong
ICONE29-88784 The Comprehensive Performance Comparison Research Between Two Types of Radiators Applied in Electronic Equipment 2022 Huang, Chonghai
ICONE29-88852 Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break 2022 Revankar, Shripad T.
ICONE29-88887 Dynamic Modeling of the Supercritical Carbon Dioxide Simple Recuperated Brayton Cycle 2022 Song, Ping
ICONE29-89471 HL1000 Nuclear Power Station Emergency Borating System Capacity Demonstration 2022 Tian, Zhaohua
ICONE29-89385 Research on Influence of Fuel Crud in Reactivity Initiated Accident 2022 Zang, Liye
ICONE29-89564 Prediction of Critical Heat Flux in Different Power Distribution of Nuclear Heatinc Reactor’s Rod Assembly 2022 Zhu, Gan
ICONE29-89486 Analysis of Leakage Flow in Shell Side of Regenerative Heat Exchanger in Chemical and Volume Control System 2022 Gong, Zili
ICONE29-90343 The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident 2022 Ke, Xiao
ICONE29-90432 Research of Supereceritical Carbon Dioxide Thermal Power System Based on Lead Cooled Fast Reactor 2022 Li, Zhihui
ICONE29-90347 Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor 2022 Li, Ang
ICONE29-90658 Experimentally Investigating Effects of Water Quality on the Critical Heat Flux for the Downward Facing Surface 2022 Zhang, Guanhong
ICONE29-91486 Experimental Assessment of RELAP5 for the Prediction of Passive Residual Heat Removal Capacity of the Intermediate Heat Exchange Loop 2022 Qi, Zhanfei
ICONE29-91530 Further Elaboration of Single Bubble Expansion Model and Analysis of Pressure Response Within Water-Glycerol System 2022 Mao, Feng
ICONE29-91668 Effect of Quantity of Inserted Small Spheres on the Heat Transfer Characteristics of a Structured Pebble Bed 2022 Chen, Leisheng
ICONE29-91755 A Mechanistic Model for Predicting the Void Fraction in a One-Side Heated Annular Channel 2022 Wen, He
ICONE29-91739 Characteristic Behavior of Flow Field in Blocked Fuel Assembly Flow Channel under Steady Flow Condition 2022 Jayeola, Mathew
ICONE29-91811 Investigation the Fuel Damage Fraction of IB-LOCA 2022 Yue, Zhidong
ICONE29-91869 Experimental Study on Natural Circulation in Pool Type Fast Reactor Using a Water Model 2022 Cheng, Daoxi
ICONE29-92118 Performance Evaluation of Typical 3-Loop PWR With Annular Fuel Assemblies Under Typical Accidents 2022 Yang, Bowen
Alle Artikel auflisten